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Aluminum-Oxide Temperatures on the Mark VB, VE, VR, 15, and Mark 25 Assemblies

Description: The task was to compute the maximum aluminum-oxide and oxide-coolant temperatures of assemblies cladded in 99 plus percent aluminum. The assemblies considered were the Mark VB, VE, V5, 15 and 25. These assemblies consist of nested slug columns with individual uranium slugs cladded in aluminum cans. The CREDIT code was modified to calculate the oxide film thickness and the aluminum-oxide temperature at each axial increment. The information in this report will be used to evaluate the potential for cladding corrosion of the Mark 25 assembly.
Date: July 17, 2001
Creator: Aleman, S.E.
Partner: UNT Libraries Government Documents Department

Old F-Area Seepage Basin Transport Analyses in Support of a SCDHEC Mixing Zone Application

Description: This report documents the groundwater flow and transport results presented in the groundwater mixing zone application (GWMZ) for the Old F-Area Seepage Basin (OFASB) submitted to the South Carolina Department of Health and Environmental Control (SCDHEC) in March, 1997 (WSRC, 1997).
Date: December 4, 1998
Creator: Aleman, S.E.
Partner: UNT Libraries Government Documents Department

Aluminum-Oxide Temperatures on the Mark VB, VE, VR, 15, and Mark 25 Assemblies

Description: The task was to compute the maximum aluminum-oxide and oxide-coolant temperatures of assemblies cladded in 99+ percent aluminum. The assemblies considered were the Mark VB, VE, V5, 15 and 25. These assemblies consist of nested slug columns with individual uranium slugs cladded in aluminum cans. The CREDIT code was modified to calculate the oxide film thickness and the aluminum-oxide temperature at each axial increment. This information in this report will be used to evaluate the potential for cladding corrosion of the Mark 25 assembly.
Date: July 17, 2001
Creator: Aleman, S.E.
Partner: UNT Libraries Government Documents Department

FACT (Version 2.0) - Subsurface Flow and Contaminant Transport Documentation and User's Guide

Description: This report documents a finite element code designed to model subsurface flow and contaminant transport, named FACT. FACT is a transient three-dimensional, finite element code designed to simulate isothermal groundwater flow, moisture movement, and solute transport in variably saturated and fully saturated subsurface porous media.
Date: May 5, 2000
Creator: Aleman, S.E.
Partner: UNT Libraries Government Documents Department

Capture Zone Analyses of Two Airlift Recirculation Wells in the Southern Sector of A/M Area

Description: This report documents a series of capture zone analyses performed to access the expected overall performance of two (of the twelve) vertical airlift recirculation wells (ARWs) (specifically, SSR-011 and SRR-012) located in the Southern Sector of A/M Area.
Date: September 14, 1999
Creator: Aleman, S.E.
Partner: UNT Libraries Government Documents Department

Subsurface Flow and Contaminant Transport Documentation and User's Guide

Description: This report documents a finite element code designed to model subsurface flow and contaminant transport, named FACT. FACT is a transient three-dimensional, finite element code designed to simulate isothermal groundwater flow, moisture movement, and solute transport in variably saturated and fully saturated subsurface porous media. The code is designed specifically to handle complex multi-layer and/or heterogeneous aquifer systems in an efficient manner and accommodates a wide range of boundary conditions. Additionally, 1-D and 2-D (in Cartesian coordinates) problems are handled in FACT by simply limiting the number of elements in a particular direction(s) to one. The governing equations in FACT are formulated only in Cartesian coordinates.
Date: July 28, 1999
Creator: Aleman, S.E.
Partner: UNT Libraries Government Documents Department

Three dimensional zone of capture analysis for the A/M-area

Description: Savannah River Technology Center personnel have performed a zone of capture analysis of the recovery well network with the A/M-Area of the Savannah River Site. The analysis includes the simulated effects of the existing and planned recovery well systems. The analysis incorporates the results of a fully three-dimensional model developed for the A/M Area with post-processing advective reverse particle tracking to evaluate the zone of capture of the recovery well system. SRTC has examined scenarios that simulate the 0-5, the 5-15, and the 15-30 year zone of capture that result from the groundwater pump and treat systems for the existing and planned recovery wells. The results of this analysis provide information regarding groundwater plume containment and control for the M-Area Aquifer Zone, the Lost Lake Aquifer Zone, and the `Middle-Sand` Aquifer Zone of the Crouch Branch Confining Unit.
Date: May 30, 1995
Creator: Jackson, D.G. & Aleman, S.E.
Partner: UNT Libraries Government Documents Department

TCE field-scale simulation using immobile-mobile waste phase model

Description: Groundwater contamination resulting from releases of chlorinated volatile organic compounds into the environment is commonplace. Industrial solvents, such as trichloroethylene (TCE), were historically released into top soils as a means of disposal. At numerous sites nationwide, cleanup efforts are underway. To evaluate the benefits associated with proposed remediation alternatives, flow and transport modeling is playing an ever increasing role. In many situations site characterization of contaminant source terms is very sketchy, resulting in a lack of necessary data to develop a reliable source term model directly from a database. As such, investigators are forced into an approach of estimating the source term in an inverse modeling fashion. Field-scale attempts are made here to predict the fate and transport of TCE under various remediation alternatives. Under a no action scenario, inverse modeling to establish the source term is performed where comparison to field measurements are made.
Date: May 1, 1997
Creator: Hamm, L. L.; Aleman, S. E. & Shadday, M. A.
Partner: UNT Libraries Government Documents Department

Modeling Ion-Exchange Processing With Spherical Resins For Cesium Removal

Description: The spherical Resorcinol-Formaldehyde and hypothetical spherical SuperLig(r) 644 ion-exchange resins are evaluated for cesium removal from radioactive waste solutions. Modeling results show that spherical SuperLig(r) 644 reduces column cycling by 50% for high-potassium solutions. Spherical Resorcinol Formaldehyde performs equally well for the lowest-potassium wastes. Less cycling reduces nitric acid usage during resin elution and sodium addition during resin regeneration, therefore, significantly decreasing life-cycle operational costs. A model assessment of the mechanism behind ''cesium bleed'' is also conducted. When a resin bed is eluted, a relatively small amount of cesium remains within resin particles. Cesium can bleed into otherwise decontaminated product in the next loading cycle. The bleed mechanism is shown to be fully isotherm-controlled vs. mass transfer controlled. Knowledge of residual post-elution cesium level and resin isotherm can be utilized to predict rate of cesium bleed in a mostly non-loaded column. Overall, this work demonstrates the versatility of the ion-exchange modeling to study the effects of resin characteristics on processing cycles, rates, and cold chemical consumption. This evaluation justifies further development of a spherical form of the SL644 resin.
Date: September 19, 2012
Creator: Hang, T.; Nash, C. A. & Aleman, S. E.
Partner: UNT Libraries Government Documents Department

DEGB LOCA ECS power limit recommendation for the K-14.1 subcycle. Revision 1

Description: This report documents assembly deposited power limits and the corresponding effluent temperature limits recommended for operating the K-14.1 subcycle to ensure sufficient cooling of reactor assemblies during the ECS phase of a Double Ended Guillotine Break (DEGSS) Loss of Coolant Accident (LOCA). The ECS LOCA effluent temperature limits are computed for each flowzone of the K-14.1 charge. The recommended overall DEGB LOCA ECS power limit is 1515 MW or about 63.1% of the historical full reactor power limit (assumed to be 2400-MW) for Mark 22 assemblies. The design basis accident is a break in the plenum inlet line where the AC pump motors not tripped.
Date: April 1, 1991
Creator: Smith, F. G. III & Aleman, S. E.
Partner: UNT Libraries Government Documents Department

FLOWTRAN-TF user guide

Description: This document is a set of detailed instructions and guidelines to aid users in constructing and interpreting FLOWTRAN-TF input and output files for version 1.2 of the source code. The document assumes the user is familiar with the FLOWTRAN-TF Software Design report, SRS fuel assembly hardware, and two-phase flow. General code capabilities and input options are summarized. Then, detailed instructions for creating and interpreting code input files are given next. A sample input deck and corresponding output files are listed for reference and illustration. FLOWTRAN-TF is a two-phase thermal-hydraulics code of similar technology to existing commercial reactor codes such as RELAP and TRAC but customized for Savannah River Site applications. The code may be used to simulate solid components, fluid coolant flow and solid-fluid heat transfer, or fluid flow only (adiabatic flow channels). Pure component water or two-component air-water flows may be modeled. A variety of materials may be chosen for the solid tubes separating flow channels. FLOWTRAN-TF is fundamentally a transient analysis tool.
Date: February 1, 1993
Creator: Flach, G. P.; Lee, S. Y. & Aleman, S. E.
Partner: UNT Libraries Government Documents Department

DEGB LOCA ECS power limit recommendation for the K-14. 1 subcycle

Description: This report documents assembly deposited power limits and the corresponding effluent temperature limits recommended for operating the K-14.1 subcycle to ensure sufficient cooling of reactor assemblies during the ECS phase of a Double Ended Guillotine Break (DEGSS) Loss of Coolant Accident (LOCA). The ECS LOCA effluent temperature limits are computed for each flowzone of the K-14.1 charge. The recommended overall DEGB LOCA ECS power limit is 1515 MW or about 63.1% of the historical full reactor power limit (assumed to be 2400-MW) for Mark 22 assemblies. The design basis accident is a break in the plenum inlet line where the AC pump motors not tripped.
Date: April 1, 1991
Creator: Smith, F.G. III & Aleman, S.E.
Partner: UNT Libraries Government Documents Department

FLOWTRAN-TF software design

Description: FLOWTRAN-TF was created to analyze an individual Mk22 fuel assembly during a large break Loss Of Coolant Accident (LOCA) scenario involving the Savannah River Site K-reactor after the initial few seconds of the transient. During the initial few seconds reactor cooling is limited by the static or Ledinegg flow instability phenomenon. The predecessor FLOWTRAN code was developed to analyze this portion of a LOCA. In the several seconds following the break, a significant fraction of the reactor coolant inventory leaks out the break, Emergency Cooling System (ECS) flow is initiated, and air enters the primary coolant circulation loops. Reactor fuel assemblies are cooled by a low flowrate air-water downflow. Existing commercial nuclear industry thermal-hydraulic codes were judged inadequate for detailed modeling of a Mk22 fuel assembly because the application involves a ribbed annular geometry, low pressure, downflow and an air-water mixture. FLOWTRAN-TF is a two-phase thermal-hydraulics code of similar technology to existing commercial codes such as RELAP and TRAC but customized for Savannah River Site applications. The main features and capabilities of FLOWTRAN-TF are detailed Mk22 fuel assembly ribbed annular geometry; conjugate heat transfer; detailed neutronic power distribution; three-dimensional heat conduction in Mk22 fuel and target tubes; two-dimensional coolant flow in channels (axial, azimuthal); single-phase and/or two-phase fluid (gas, liquid and/or gas-liquid); two-component (air, water); constitutive models applicable to low pressure air-water downflow in ribbed annular channels. The design of FLOWTRAN-TF is described in detail in this report which serves as the Software Design Report in accordance with Quality Assurance Procedure IV-4, Rev. 0 ``Software Design and Implementation`` in the 1Q34 manual.
Date: February 1, 1993
Creator: Aleman, S. E.; Flach, G. P.; Hamm, L. L.; Lee, S. Y. & Smith, F. G. III
Partner: UNT Libraries Government Documents Department

FLOWTRAN-TF software design

Description: FLOWTRAN-TF was created to analyze an individual Mk22 fuel assembly during a large break Loss Of Coolant Accident (LOCA) scenario involving the Savannah River Site K-reactor after the initial few seconds of the transient. During the initial few seconds reactor cooling is limited by the static or Ledinegg flow instability phenomenon. The predecessor FLOWTRAN code was developed to analyze this portion of a LOCA. In the several seconds following the break, a significant fraction of the reactor coolant inventory leaks out the break, Emergency Cooling System (ECS) flow is initiated, and air enters the primary coolant circulation loops. Reactor fuel assemblies are cooled by a low flowrate air-water downflow. Existing commercial nuclear industry thermal-hydraulic codes were judged inadequate for detailed modeling of a Mk22 fuel assembly because the application involves a ribbed annular geometry, low pressure, downflow and an air-water mixture. FLOWTRAN-TF is a two-phase thermal-hydraulics code of similar technology to existing commercial codes such as RELAP and TRAC but customized for Savannah River Site applications. The main features and capabilities of FLOWTRAN-TF are detailed Mk22 fuel assembly ribbed annular geometry; conjugate heat transfer; detailed neutronic power distribution; three-dimensional heat conduction in Mk22 fuel and target tubes; two-dimensional coolant flow in channels (axial, azimuthal); single-phase and/or two-phase fluid (gas, liquid and/or gas-liquid); two-component (air, water); constitutive models applicable to low pressure air-water downflow in ribbed annular channels. The design of FLOWTRAN-TF is described in detail in this report which serves as the Software Design Report in accordance with Quality Assurance Procedure IV-4, Rev. 0 Software Design and Implementation'' in the 1Q34 manual.
Date: February 1, 1993
Creator: Aleman, S.E.; Flach, G.P.; Hamm, L.L.; Lee, S.Y. & Smith, F.G. III.
Partner: UNT Libraries Government Documents Department

High Level Waste System Impacts from Small Column Ion Exchange Implementation

Description: The objective of this task is to identify potential waste streams that could be treated with the Small Column Ion Exchange (SCIX) and perform an initial assessment of the impact of doing so on the High-Level Waste (HLW) system. Design of the SCIX system has been performed as a backup technology for decontamination of High-Level Waste (HLW) at the Savannah River Site (SRS). The SCIX consists of three modules which can be placed in risers inside underground HLW storage tanks. The pump and filter module and the ion exchange module are used to filter and decontaminate the aqueous tank wastes for disposition in Saltstone. The ion exchange module contains Crystalline Silicotitanate (CST in its engineered granular form is referred to as IONSIV{reg_sign} IE-911), and is selective for removal of cesium ions. After the IE-911 is loaded with Cs-137, it is removed and the column is refilled with a fresh batch. The grinder module is used to size-reduce the cesium-loaded IE-911 to make it compatible with the sludge vitrification system in the Defense Waste Processing Facility (DWPF). If installed at the SRS, this SCIX would need to operate within the current constraints of the larger HLW storage, retrieval, treatment, and disposal system. Although the equipment has been physically designed to comply with system requirements, there is also a need to identify which waste streams could be treated, how it could be implemented in the tank farms, and when this system could be incorporated into the HLW flowsheet and planning. This document summarizes a preliminary examination of the tentative HLW retrieval plans, facility schedules, decontamination factor targets, and vitrified waste form compatibility, with recommendations for a more detailed study later. The examination was based upon four batches of salt solution from the currently planned disposition pathway to treatment in the SCIX. Because ...
Date: August 18, 2005
Creator: McCabe, D. J.; Hamm, L. L.; Aleman, S. E.; Peeler, D. K.; Herman, C. C. & Edwards, T. B.
Partner: UNT Libraries Government Documents Department

FLOWTRAN-TF v1.2 source code

Description: The FLOWTRAN-TF code development effort was initiated in early 1989 as a code to monitor production reactor cooling systems at the Savannah River Plant. This report is a documentation of the various codes that make up FLOWTRAN-TF.
Date: February 1, 1993
Creator: Aleman, S. E.; Cooper, R. E.; Flach, G. P.; Hamm, L. L.; Lee, S. & Smith, F. G. III
Partner: UNT Libraries Government Documents Department

FLOWTRAN-TF v1. 2 source code

Description: The FLOWTRAN-TF code development effort was initiated in early 1989 as a code to monitor production reactor cooling systems at the Savannah River Plant. This report is a documentation of the various codes that make up FLOWTRAN-TF.
Date: February 1, 1993
Creator: Aleman, S.E.; Cooper, R.E.; Flach, G.P.; Hamm, L.L.; Lee, S. & Smith, F.G. III.
Partner: UNT Libraries Government Documents Department